Masahiko Nakase

Improved core design and integrated back-end fuel cycle scheme for 200 MWt marine molten chloride fast reactor

This study presents an improved core design and the introduction of integrated back-end fuel cycle scheme for a 200 MWt Molten Chloride Fast Reactor (MCFR) intended as nuclear marine propulsion. The objective is to increase fuel burnup and reducing uranium consumption whilst main...

Prediction of plutonium content of BWR/MOX fuel using a neural network

The Nuclear Material Balance (NMB) code is a comprehensive nuclear fuel cycle simulator developed by the Institute of Science Tokyo and the Japan Atomic Energy Agency. By modeling a fleet of reactors, fuel cycle simulators like NMB can help to optimize uranium and plutonium utili...

Trade-off between repository footprint and radiotoxicity in geological disposal of vitrified high-level waste from spent MOX fuels: quantitative assessment of simplified minor actinide separation

Radioactive waste management remains a critical challenge for the sustainability of nuclear energy systems, particularly for closed fuel cycles utilizing mixed oxide (MOX) fuel. MOX fuel contains significantly higher concentrations of minor actinides (MAs) and heat-generating nuc...